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• W2574493658 abstract "Routing neptunium to a single product in spent nuclear fuel reprocessing is a significant challenge. In this work, we have further improved the simulation of neptunium extraction in an advanced PUREX flowsheet by applying a revised model of the Np(V)–Np(VI) redox reaction kinetics, a new nitric acid radiolysis model, and by evaluating various models for the nitrous acid distribution coefficient. The Np disproportionation reaction is shown to have a negligible effect. The models are validated against published ‘cold test’ experimental results; the ‘hot test’ simulation suggests that high neptunium radiolysis could help to achieve high recoveries using this flowsheet." @default.
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• W2574493658 date "2017-01-02" @default.
• W2574493658 modified "2023-09-30" @default.
• W2574493658 title "Simulation of Neptunium Extraction in an Advanced PUREX Process—Model Improvement" @default.
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• W2574493658 doi "https://doi.org/10.1080/07366299.2016.1273684" @default.
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